ML19296D005
| ML19296D005 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/09/1980 |
| From: | Clemons P, Crocker H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19296D000 | List: |
| References | |
| 50-271-79-22, NUDOCS 8002290202 | |
| Download: ML19296D005 (7) | |
See also: IR 05000271/1979022
Text
.
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
Region I
Report No.
50-271/79-22
Docket No.
50-271
License No. DPR-28
Priority
--
Category
C
Licensee:
Vermont Yankee Nuclear Power Corporation
20 Turnpike Road
Westborough, Massachusetts 01581
Vermont Yankee Nuclear Power Station
Facility Name:
Inspection at:
Vernon, Vermont
Inspection conducted:
December 5-6, 1979
Inspectors: [
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P. Clemons, Radiation Specialist
date signed
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date signed
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Chief, Radiatiun Suppor[
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Section, Fuel Facilities and Materials
Safety Branch
Inspection Summary:
Inspection on December 5-6,1979 (Report No. 50-271/79-22)
Areas Inspected:
Special unannounced inspection by a regional based
inspector of the licensee's response to Bulletin 79-19, including:
regulatory requirements, burial site requirements, procedures, training,
audits, records of shipments, onsite observations, and discrepant shipping
reports.
Results:
No items of noncompliance or-deviations were disclosed.
Region I Form 12
(Rev. April 77)
8002290 2O2
.
.
DETAILS
1.
Persons Contacted
Principal Licensee Emoloyees
Mr. D. Girroir, Technical Assistant
Mr. R. Leach, Health Physicist
Mr. W. Murphy, Assistant Plant Superintendent
Mr. G. Weyman, Chemistry and Health Physics Supervisor
The inspector reviewed Vermont Yankee's response to IE Bulletin No. 79-19
in-office to assure that all information required by the bulletin was
included and to ascertain if corrective action commitments were also included.
The Health Physicist is the individual responsible for the safe, transfer,
packaging and transport of low level radioactive waste material.
2.
Reaulatory Documents
The inspector verified that the licensee has a set of DOT and NRC regu-
lations.
The licensee maintains a copy of 10 CFR from the U.S. Government
Printing Office, Superintendent of Documents as part of a subscription
service.
This service apparently assures that the 10 CFR is maintained
current.
The licensee does not have a similiar subscription service for 49
CFR therefore this document is not maintained current.
The inspector noted that the licensee does have a current copy of the R. M.
Graziano document that is published by the Bureau of Explosives, and the
inspector was informed that this document is maintained current by a sub-
scription service.
3.
Burial Site Requirements
According to a licensee representative waste shipments are made only to the
burial site in South Carolina.
At the inspector's request, he was shown a
copy of Chem-Nuclear's License No. 097, that was issued by the State of
The inspector also reviewed a copy of the burial site
criteria that the licensee possessed with an effective date of December 1, 1979.
4.
Procedures
In response to IE Bulletin 79-19, the licensee stated that all radioactive
material is processed and packaged in accordance with written, management
approved procedures.
3
The inspector reviewed the following procedures to determine if they were
approved:
"Radwaste Cask Handling"
Procedure No. 0.P.-2511, Revision 5
" Shipment and Receipt of Radioactive Materials"
Procedure No. A.P.-0504, Revision 5
" Solid Radwaste"
Procedure No. 0.P.-2153, Revision 4
All of the procedures had been approved by the Plant Operating Review
Committee (PORC).
Accordir.g to a licensee representative the procedure" cited above,
represents the sum total of all procedures governing radioactive waste.
The " Solid Radwaste" procedure is specific for the Auxiliary Operators
who are transferring the waste from the primary coolant clean-up system,
floor drains and equipment drains, etc.
The other two procedures are
directed toward health physics personnel.
5.
Training
In responding to IE Bulletin 79-19 the licensee stated:
" Training and periodic retraining covering NRC and D0T requirements, and
applicable plant procedure requirements is provided for all employees
involved in the transfer packaging and transport of radioactive material.
Records of this training are maintained."
The inspector reviewed records that indicated health physics personnel
received training in plant procedures and 00T regulations in November
1978.
The records did not indicate that these employees received
training in 10 CFR 71 regulations.
4
The records did not indicate that Auxiliary Operators received any
training in 1978 and these are personnel who are required to transfer
the waste from the various systems to the centrifuge.
The licensee has agreed to provide training and periodic retraining
covering flRC and DOT regulations, applicable plant procedures, waste
burial license requirements, and minimizing low level waste to appro-
priate personnel.
In addition to the training provided by the licensee, according to a
licensee representative, they are also considering a seminar presented
by the fluclear Energy Waste Management Consultants (fiEWC). A proposed
seminar agenda includes:
types of regulations (00T, f4RC, 00E, IAEA,
etc.), responsibilities as a shipper, applying the regulations (hazardous
materials tables, definitions - LSA, etc.), types of shipments, and
emergency responses.
6.
Audit
The inspector verified that the licensee has implemented an audit
program of activities associated with the transfer, packaging, and
transport of low level radioactive wastes.
The inspector reviewed the
audit report, 79-3-A, of the audit performed on October 11, 1979.
The inspector questioned a licensee representative about the quali-
fications of the two individuals performing the audit.
The inspector
was told that the two individuals were from the corporate office.
The
inspector asked if the individuals had experience in the areas to be
audited.
He was told that the individuals had been employed in the
nuclear industry for several years, but that they did not possess
extensive expertise in the areas to be audited.
The inspector noted
that in order for an audit to be adequate, the auditors must be
familiar with what is being audited.
7.
Records Of Shipments
As the inspector reviewed licensee shipping records, he observed two
shipments made during the month of October 1979.
He noted that Ship-
ment flo. 79-20 made on or about October 15, 1979 contained approximately
580 curies of radioactive waste.
Shipment fio. 79-22 made on or about
October 16, 1979, contained approximately 12 curies of radioactive
waste.
5
'u nt No. 79-20 was made in the Hittman HN-200 cask, and Shipment No.
7 M 2 was made in the Hittmann HN-100 cask.
Noting that both shipments
exceeded Type A quantities, the inspectnr requeste:1 copies of the
Certificates of Compliance.
The inspector was given a copy of
Certificate of Compliance No. 6574, Revision 3, for the HN-200 cask and
Certificate of Compliance No. 9086, Revision 4, for the HN-100 cask.
The inspector noted that each Certificate of Compliance referenced other
documents.
10 CFR 71.12 establishes a general license for delivery to a
carrier for transport:
"(b)
In a package for which a license, certificate of compliance or
other approval has been issued by the Commission's Director of
Nuclear Material Safety and Safeguards for the Atomic Energy
Commission, provided that:
(1) The person using a package pursuant to the general license
provided by this paragraph:
(i) Has a copy of the specific license, certificate of
compliance, or other approval authorizing use of the
package and all documents referred to in the license,
certificate, or other approval, as applicable..."
The inspector requested to see copies of all of the referenced documents
inasmuch as the regulations requires licensees to have copies of all such
documents prior to shipping.
A licensee representative provided the
inspector with copies of all of the referenced documents.
No items of noncompliance were identified.
8.
Onsite Observations
On December 5, 1979, the inspector toured all areas associated with
radioactive waste operations.
The inspector noted that no operations
were being performed involving the rad-waste system.
He noted that one
HN-100 cask had been received onsite and was awaiting to be filled with
spent resin.
.
6
9.
Discrepant Reports
The inspector discussed three Radioactive Waste Shipment Discrepancy Reports
with a licensee representative.
Two of the reports were concerned with
about 1.5 gallons of free standing liaulds in two HN-100 casks, and the
third report was concerned with contamination on the floor of a van containing
solidified waste in 55 gallon metal drums.
The representative informed the inspector that the HN-100 cask has a liner
that is placed inside the cask to receive the spent resin.
He stated that
as soon as the liner is filled with resin, it is washed inside the cask
using water from a hose. The HN-100 has a plug in its bottom which is
removed to drain the water used to wash the liner.
The licensee representative
stated that it is residual water from the liner washing that is not completely
drained from the HN-100 cask, that was observed at the burial site as the
liner was removed from the shipping cask.
With reference to the contamination on the floor of the van, the licensee
representative stated that the 55 aallon drums were thoroughly monitored
and found to be within acceptable limits prior to being loaded onto the
van.
The licensee representative stated that the containers were strong,
tight packages at the time of shipment and they did not leak causing the
contamination.
The inspector asked if the McCormack van (closed van No. 304) had been
monitored upon receipt on site, and he was told that the van was not monitored
upon receipt.
The inspector told the licensee representative that the van
should have been monitored upon receipt on site, and inasmuch as it was not
monitored, the licensee cannot refute the burial site accusation.
The corrective action taken by the licensee in the two cited cases are as
follows:
1.
All vans used for shipping radioactive waste material shall be monitored
upon receipt onsite.
2.
The liners used in the HN-100 cask, will not be washed.
They will be
enclosed in plastic within the cask, and once the resins are loaded
into the liner, the liner will be completely covered with plastic
within the container.
.
.
7
10.
Exit Interview
The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on December 6, 1979.
The inspector
summarized the purpose and scope of the inspection, and the findings as
presented in this report.